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This presentation explores the real-time simulator as a platform for severe accident simulation and how it can be used to address post-Fukushima challenges in the nuclear energy industry. Presented at ANS PSA International Topical Meeting. For more information, go to GSES.com and follow GSE Systems on Twitter @GSESystems and Facebook.com/GSESystems. Thanks for viewing!
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Simulator Platform for Multi-Unit Severe Accident Simulation
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• Real-time simulator
• Post-Fukushima challenges
• Simulator technology
• Case studies for multi-unit plant site
Outlines
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• Real-time simulators came to the nuclear industry as training tools in the 1970s– Full plant modeled, but models often “hand crafted”– Analog controls, traditional hard panel control panels
• Today’s NPP simulator is high-fidelity– Same scope, but…– Engineering-grade computer codes, such as RELAP, MAAP, S3R– Digital controls and modern HSIs– Holistic dynamic plant model:
- Multi-physics, multi-systems, multi-codes, multi-units
Real-Time Simulator
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• Broad or full-scope plant model– Includes primary, secondary, safety systems, balance-of-plant,
electrical systems, I&C, etc.– Normal operation, transients, design-basis accident
• All models integrated and synchronized (coupling)
• 1 second of problem time = 1 second of real time (feels like the real plant)
• Models are interactive– Observed and operated like the real plant– Can be integrated with real control systems
Real-Time Simulator
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Post-Fukushima New Recommendations & Requirements
Multi-Unit Events, PRA
Beyond Design-Basis
Extended SBO
FLEX
New Mitigation Strategies
Predictive Response
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Simulator Technology for Resource Alignment
• Common technology for:– Engineering– Risk assessment– Operations– Training– Emergency planning– Local authorities and regulators– Full-scope simulator for operator training
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• Running third-party best estimate analysis codes as integral parts of simulators
• Enforce synchronization between multiple systems and human interactions
• Maintain code integrity and repeatability
• Have access to internal memory and variables
• Advanced 2D, 3D visualization interfaces
• Post-data processing tools with database
• Multiple processors and computers
GSE High-Definition Platform
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Parallel Architecture for MAAP and MELCOR
JADE Operation StationDCS-Like HMI Animation,Soft Panels,
Interface Simulation Control
HD Server 1 for MAAP5, Unit 1
HD Server 2 for MAAP5, Unit 2
HD Server 3 for MAAP5, Unit 3
JADE Dashboard (JDB)HD server
Graphical User InterfaceInteractive Control,
Monitor, V&V
HD Client
HD Server 4 for MELCOR, Unit 1
HD Server 5 for MELCOR, Unit 2
HD Server 6 for MELCOR, Unit 3
HD Server 7 for MACCS2, Site
HD Server 8 for RASCAL, Site
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Main Simulation Processes
freeze
Create restart or update input decks: PyGI
Start HD Executive
Read Input or Restart Decks
Initialize 3rd Party Engineering Code
Run a Frame
Interactive User
Actions
HD IC Files
reset
snap
End
Text Edit Output
Input or Restart File
Start 3rd Party Engineering
Code Batch Job
Read Input or Restart Decks
Initialize 3rd Party Engineering Code
Run the Whole Job
End
Scheduled Time end
exit
3rd Party Engineering
Code
Scheduled
Interactive simulations with MAAP and MELCOR in the same HD platform
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JADE DashBoard (JDB)
Host and executive connection Executive control Trending/Data
Collection
Executive modulesListed output and command line
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V&V Tool
MAAP
MELCOREasy to compare MAAP and MELCOR results
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Graphical SAMGs
Computer-based procedures help automate the SAMG to control the sequence of events in PSA-HD simulation
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• Used MAAP code as analytical and modeling tool
• Developed in collaboration with EPRI and ERIN Engineering
Fukushima Multi-Unit Accidents
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Fukushima Unit 1 at 3H:38M & 11H:11M
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Fukushima Unit 2 at 76H & 120H
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Fukushima Unit 3 at 76H & 120H
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Ex-plant DOSE Simulation
In-plant DOSE Simulation In-plant DOSE Simulation
Auxiliary Building
Unit 1 Containment Unit 2 Containment
Spent Fuel Pool
Core
RCSSG
Core
SGRCS
MAAP5
MAAP5
MAAP5
PWR with 2 Units and Spent Fuel
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Loss of All AC Power with FLEX Pump Operation
FLEX Portable Diesel Generator
SG 1SG 2
SG 4
SG 3
s3.rar
G
External Water Source
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Loss of All AC Power – SG#1/3
Levels kept by FLEX pumps at 50M
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UNIT 1 UNIT 2
Time 3H:36M
Reactor Core at 3H:36M
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Time 6H:23M:46S
Unit 2 Containment & Flammability at 6H:23M
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Time 6H:20M:45S
Off-Site Radiological Dose at 6H:20M
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Integrated EOPs, SAMGs, etc.
Full-scope Simulator (RELAP5-HD) MAAP
NOPs EOPs SAMGs
Emergency Director(Plant Manager)
Local Field Personnel
Main Control RoomTechnical Support
CenterRadiological
Center
Postulated Actions Exercises
Realistic Training Expanded Training
Other codes
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EPRI MAAP Code
• ''MAAP 5.0 is an Electric Power Research Institute (EPRI) software program that performs severe accident analysis for nuclear power plants including assessments of core damage and radiological transport. A valid license to MAAP 5.0 from EPRI for customer's use of MAAP 5.0 is required prior to a customer being able to use MAAP 5.0 with [LICENSEE PRODUCT].
• EPRI (www.epri.com) conducts research and development relating to the generation, delivery and use of electricity for the benefit of the public. An independent, nonprofit organization, EPRI brings together its scientists and engineers as well as experts from academia and industry to help address challenges in electricity, including reliability, efficiency, health, safety and the environment. EPRI does not endorse products or services, and specifically does not endorse [NEW PRODUCT NAME] or GSE. Interested vendors may contact EPRI for a license to MAAP 5.0."
For more information:
Go to: www.GSES.com
Call: 800.638.7912
Email: [email protected]
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Twitter @GSESystems
Facebook.com/GSESystems